ML19045A526

Enclosure 1: Certificate of Compliance No. 9186, Rev. No. 19 (Letter to R. Pratt Model S-6213 Power Unit Shipping Container)

ML19045A526
Person / Time
Site:	07109186
Issue date:	02/13/2019
From:	John Mckirgan Spent Fuel Licensing Branch
To:	US Dept of Energy (DOE)
White B
Shared Package
ML19045A523	List: ML19045A525 ML19045A526
References
EPID L-2018-LLA-0171
Download: ML19045A526 (5)

Text

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9186 19 71-9186 USA/9186/B(U)F-96 1 OF 5

2. PREAMBLE

a. This certificate is issued to certify that the package (packaging and contents) described in Item 5 below meets the applicable safety standards set forth in Title 10, Code of Federal Regulations, Part 71, Packaging and Transportation of Radioactive Material.

b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION

a. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Safety Analysis for Shipping S8G Power Units in U.S. Department of Energy the S-6213 Container, Rev. 7, dated Division of Naval Reactors June 16, 1975, as supplemented; and Safety Washington, DC 20858 Analysis for Shipment of S6W Shipboard Power Units in the Model 2 S-6213 PUSC, as supplemented.

4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging (1) Model Nos.: Model 1, S-6213 Power Unit Shipping Container Model 2, S-6213 Power Unit Shipping Container (2) Description A power unit shipping container (PUSC) for shipment of a power unit complete with control rods and control rod drive mechanisms installed.

The Model 1 S-6213 PUSC consists of a carbon steel cylindrical shell approximately 9-1/4 feet in outside diameter by 39-1/2 feet long, including hemispherical steel end impact limiters, with 10-3/4-foot outside diameter central flanges joining the barrel and cover halves.

The Model 2 S-6213 PUSC is of the same design as the Model 1, except that the primary container material is HY-80 steel. A power unit is supported in the PUSC by a centrally located thick circular steel plate (PU head) which is clamped between the central mating flanges of the PUSC and fastened by 94, 2-inch diameter high strength studs. The upper and lower extremities of the power unit cantilever into the barrel and cover halves without additional support. A lower support adapter is installed in the barrel end of the container during shipment of the S6W shipboard power unit. A shipping/lifting ring, a flange adapter, and a lower support adapter are installed in the container during shipment of the S9G shipboard power unit. An adaptor ring is installed in the container during shipment of the S8GP/TDC power unit.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9186 19 71-9186 USA/9186/B(U)F-96 2 OF 5 5.(a) Packaging (Continued)

(2) Description The PUSC is shipped in the horizontal position on a support frame which is secured to a specially built flatbed rail car.

The weight of the PUSC, including frame and contents, is approximately 429,900 pounds for shipment of the S6W shipboard power unit, and 329,000 pounds for shipment of the S9G shipboard power unit. The loaded weight of the S8GP/TDC power unit is approximately 340,600 pounds.

(3) Drawings The Model 1 and Model 2 S-6213 PUSC are constructed in accordance with the Drawings included in the applications (see references, below).

5.(b) Contents (1) Type and form of material (i) Unirradiated S6W advanced fleet reactor shipboard power unit as described in Chapter 6 of "S6W Prototype Power Unit in S-6213 Power Unit Shipping Container Safety Analysis Report" WAPD-REO(c)1219, Revision 1, and containing uranium enriched in the U-235 isotope.

(ii) Unirradiated S9G shipboard power unit, as described in Chapter 6 of "S9G Shipboard Power Unit in S-6213 Power Unit Shipping Container Safety Analysis Report For Packaging, Revision 2, and containing uranium enriched in the U-235 isotope.

(iii) Unirradiated S9G power unit containing the Virginia Forward Fit Core, as described in supplement dated June 22, 2015.

(iv) Unirradiated S8GP/Technology Demonstration Core (TDC) power unit as described in the supplement dated June 13, 2018.

(2) Maximum quantity of material per package For the Model 1 S-6213 PUSC:

One S9G Shipboard Power Unit, or One S9G Power Unit containing Virginia Forward Fit Core.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9186 19 71-9186 USA/9186/B(U)F-96 3 OF 5 5.(b)(2) (Continued)

For the Model 2 S-6213 PUSC:

One S6W Advanced Fleet Reactor Shipboard Power Unit, One S9G Shipboard Power Unit, One S9G Power Unit containing Virginia Forward Fit Core, or One S8GP/TDC Power Unit 5.(c) Criticality Safety Index (CSI):

Minimum CSI to be shown on label for nuclear criticality control: 100

6. All control rods shall be restrained in the power unit fuel cells by the control rod holddown latches.

7. Transport by air of fissile material is not authorized.

8. For the Model 1 S-6213 PUSC, a nondestructive examination of the entire length of both inner and outer surfaces of the four tie-down support bracket-to-container wall butt welds shall be conducted prior to each loaded shipment.

(a) The nondestructive examination in accordance with a written procedure may be by either:

(1) The liquid penetrant method in accordance with:

(i) Article 6,Section V, ASME Code, or (ii) MIL-STD-271E, "Nondestructive Testing Requirements for Metals," Section 5, October 31, 1973, or (iii) NAVSHIPS 250-1500-1, "Welding Standard," Section 12.5 (2) or the magnetic particle method in accordance with:

(i) Article 7,Section V, ASME Code (Yoke Technique; Dry Particle Method; direct or rectified current), or (ii) MIL-STD-271E, Section 4; specifically 4.3.1 (General) and 5.6.1(coatings),

4.3.3 (Dry Powder), 4.3.3.3.6 (Continuous), and 4.3.3.3 (Procedure) as excepted by using direct or rectified current, 4.3.3.3.3 (Yoke Technique),

4.3.2.5 (sensitivity and cleaning), and 4.3.1.3 (smoothness), or (iii) NAVSHIPS 250-1500-1, Section 12.4, 12.4.1 (General), 12.4.3 (Dry powder), 12.4.3.3.2.1 (Yoke Technique) using direct or rectified current.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9186 19 71-9186 USA/9186/B(U)F-96 4 OF 5 (b) If any indications, as defined in accordance with either:

(1) Paragraph UA-93(a), Appendix VIII, Division 1,Section VIII, ASME Code (with 7(b)(2)(i), above), or (2) Paragraphs UA-72 and UA-73, Appendix VI, Division 1,Section VIII, ASME Code (with 7(b)(2)(i), above), or (3) Class 1 acceptance criteria of NAVSEA 0900-LP-003-8000, "Surface Inspection Acceptance Standards for Metal," with Change 2, July 1, 1974 (with 7(b)(1)(ii) or 7(b)(2)(ii), above), or (4) NAVSHIPS 250-1500-1, Section 10.3.2 (with 7(b)(1)(iii) or 7(b)(2)(iii), above), as noted, are detected, the packaging shall be repaired and reinspected prior to use and shall be inspected prior to each shipment thereafter. Any defects shall be reported in accordance with 10 CFR §71.95.

9. Expiration date: March 31, 2022.

REFERENCES For the Model 1 S-6213 PUSC:

U.S. Naval Reactors application dated July 24, 1975.

Supplements dated: June 3, 1977; July 24, 1978; Naval Reactors letter G#C89-2838, dated May 22, 1989; Naval Reactors letter G#C90-03664, dated September 5, 1990; Naval Reactors letter G#92-03563, dated June 17, 1992; and Naval Reactors letter G#C92-03714, dated October 2, 1992; Naval Reactors letter G#97-03425, dated February 7, 1997; Naval Reactors letter G#C97-03614, dated September 29, 1997; Naval Reactors letter G#01-03619, dated December 11, 2001; Naval Reactors letter G#06-04833, dated December 18, 2006; Naval Reactors letter G#C08-00667, dated March 13, 2008; Naval Reactors letter G#11-04084, dated September 20, 2011; Naval Reactors letters G#C15-02760 dated June 22, 2015, and G#C01632 dated April 13, 2016; Naval Reactors letter G#16-04427, dated September 20, 2016; and Naval Reactors letter G#C18-02888, dated June 13, 2018.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9186 19 71-9186 USA/9186/B(U)F-96 5 OF 5 For the Model 2 S-6213 PUSC:

U.S. Naval Reactors application G#C91-11165, dated December 19, 1991.

Supplements dated: Naval Reactors letter G#92-03563, dated June 17, 1992; and Naval Reactors letter G#C92-03714, dated October 2, 1992; Naval Reactors letter G#97-03425, dated February 7, 1997; Naval Reactors letter G#C97-03614, dated September 29, 1997; Naval Reactors letter G#01-03619, dated December 11, 2001; Naval Reactors letter G#06-04833, dated December 18, 2006; Naval Reactors letter G#C08-00667, dated March 13, 2008; Naval Reactors letter G#11-04084, dated September 20, 2011; Naval Reactors letters G#C15-02760 dated June 22, 2015, and G#C01632 dated April 13, 2016; Naval Reactors letter G#16-04427, dated September 20, 2016; and Naval Reactors letter G#C18-02888, dated June 13, 2018.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

/RA/

John McKirgan, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Dated: 2/13/19.